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Monte Carlo Simulation Based on SCC Test Results in Hydrogenated Steam Environment for Alloy 600

  • Yohei SakakibaraEmail author
  • Ippei Shinozaki
  • Gen Nakayama
  • Takashi Nan-Nichi
  • Tomoyuki Fujii
  • Yoshinobu Shimamura
  • Keiichiro Tohgo
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)

Abstract

We investigated the applicability of a stress corrosion cracking (SCC) engineering model and simulation method developed on the basis of the SCC of sensitized 304 stainless steel in a simulated BWR environment to the primary water stress corrosion cracking (PWSCC). We conducted a uniaxial constant loading test on Alloy 600 in a 400 °C hydrogenated steam environment and found that the number of cracks observed on a specimen surface after every passage of 450 h could be approximated to Poisson distribution, indicating that a Poisson random process model is applicable to the SCC in this system. By applying the engineering model, we statistically processed experimental data by assuming that the time distribution of occurrence of microcracks follows exponential distribution, and then obtained input data for the SCC simulation. Using coalescence coefficient, k, as a fitting parameter to obtain a reasonable k-value, it was found that the best agreement between the experimental and simulation results for the number of microcracks and the maximum crack length at k = 0.15. This is about one third the k-value of 0.5 found in sensitized 304 stainless steel in the BWR environment, indicating that coalescence is more subdued in PWSCC than in SCC in the BWR environment.

Keywords

PWSCC Nickel base alloy Hydrogenated steam UCL Monte-Carlo simulation Exponential distribution Initiation Coalescence 

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Copyright information

© The Minerals, Metals & Materials Society 2019

Authors and Affiliations

  • Yohei Sakakibara
    • 1
    Email author
  • Ippei Shinozaki
    • 1
  • Gen Nakayama
    • 1
  • Takashi Nan-Nichi
    • 2
  • Tomoyuki Fujii
    • 3
  • Yoshinobu Shimamura
    • 3
  • Keiichiro Tohgo
    • 3
  1. 1.IHI Corporation Research LaboratoryIsogo-Ku, YokohamaJapan
  2. 2.IHI Corporation Nuclear Power OperationsIsogo-Ku, YokohamaJapan
  3. 3.Department of Mechanical EngineeringShizuoka UniversityNaka-Ku, HamamatsuJapan

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